Text

Monthly Operating Repts for Apr 1995 for Quad Cities Nuclear Power Station Units 1 & 2
	ML20083L409
Person / Time
Site:	Quad Cities
Issue date:	04/30/1995
From:	Moore K; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20083L406	List: ML20083L403; ML20083L409; ML20083L414;
References
	NUDOCS 9505180342
	Download: ML20083L409 (19)
	v • d • e

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k QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT April 1995

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IOWA-ILLIN0IS GAS & ELECTRIC COMPANY i

i NRC DOCKET NOS. 50-254 AND 50-265 I

LICENSE NOS. DPR-29 AND DPR-30 I

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9505180342 950505 PDR ADOCK 05000254 R

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.c TABLE OF CONTENTS I.

Introduction II.

Summary of Operating Experience A.

Unit One B.

Unit Two III.

Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A.

Amendments to Facility License or Technical Specifications B.

Facility or Procedure Changes Requiring NRC Approval C.

Tests and Experiments Requiring NRC Approval IV.

Licensee Event Reports V.

Data Tabulations A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions VI.

Unique Reporting Requirements A.

Main Steam Relief Valve Operations B.

Control Rod Drive Scram Timing Data VII.

Refueling Information VIII.

Glossary I

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INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in -

Cordova, Illinois. The Station is jointly owned by Commonwealth Ediscr.

Company and Iowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors.

The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors.

The Mississippi River is the condenser cooling water source. The plent is subject to license numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, respectively; put ant to Docket Numbers 50-254 and 50-265. The date of initial Reactor crit :alities for Units One and Two, respectively were October 18, 1971, and April 26, 1972.

Commercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 for unit Two.

This report was compiled by Kristal Moore and Debra Kelley, telephone number 309-654-2241, extensions 3070 and 2240.

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II.

SUMMARY

OF OPERATING EXPERIENCE A.-

Unit One Quad Cities Unit One began the month of April 1995 at full power and remained on line for the entire month.. Several load drops were performed, however the average daily power level remained at 80% or greater.

B.

Unit Two Quad Cities Unit Two spent the entire month of April 1995 shutdown in Refuel Outage Q2R13. The scheduled startup is June 5, 1995.

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1 III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE-A.

Amendments to Facility License or Technical Specifications There were no Amendments to the Facility License or Technical Specifications for the reporting period.

B.

Facility or Procedure Chanaes Reauirina NRC Acoroval There were no Facility or Procedure changes requiring NRC approval for the reporting period.

C.

Tests and Experiments Reauirina NRC Acoroval There were no Tests or Experiments requiring NRC approval for the reporting period.

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o IV.

LICENSEE EVENT REPORTS The following is a tabular 'ummary of all licensee event rcports. for Quad-Cities Units One and Two oscurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

UNIT 1 Licensee Event Reoort Number h

Title of occurrence There were no licensee event reports for Unit 1 for this reporting period.

UNIT 2 Licensee Event Report Number h

Title of occurrence There were no licensee event reports for Unit 2 for this reporting period.

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DATA TABULATIONS The following data tabulations are presented in this report:

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Operating Data Report B.

Average Daily Unit Power Level l

C.

Unit Shutdowns and Power Reductions A

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a APPENDIX C OPERATING DATA REPORT DOCKET No.

50 254

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UNrr One DATE May 5,1995 COMPLETED BY Kristal Moore

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TELEPHONE (309) 654-2241 i

OPERATING STATUS 0000 040195

1. REPORTING PERIOD: 2400 043095 GROSS HOURS IN REPORTING PERIOD: 719

2. CURRENTLY AUTHORIZED POWER LEVEL (MW): 2511 MAX > DEPEND > CAPACTTY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789

3. POWER LEVEL TO WHICH RESTRICTED OF ANY)(MWe-Net): N/A

4. REASONS FOR RESTRICTION OF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTriCAL 719.00 2647.80 155080.30

6. REACTOR RESERVE SHirrDOWN HOURS 0.00 0.00 3421.90

7. IIOURS GENERATOR ON LINE 719.00 2592.00 150415.90

8. UNIT RESERVE SIIUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERM AL ENERGY GENERATED (MWH) 1779131.50 6137673.00 325293796.40

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 575968.00 1981862.00 105445716.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 556271.00 1902511.00 99490677.00

12. REACTOR SERVICE FACTOR 100.00 91.97 76.75 i

13. REACTOR AVAILABILITY FACTOR 100.00 91.97 78.45

14. UNrr SERVICE FACTOR 100.at 90.03 74.44

15. UNTT AVAILABILITY FACTOR 100.00 90.03 74.89

16. UNrr CAPACTTY FAcrOR (Using MDC) 100.61 85.93 64.03 j

17. UNTT CAPACITY FACTOR (Uning Design MWe) 98.06 83.75 62.41

18. UNIT FORCED OITTAGE RATE 0.00 9.97 7.53

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP:

21. UNrrS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INIrlAL CRrrlCALTrY l

INTTIAL ELECTRICrrY COMMERCIAL OPERATION 1.16-F TliCHOP3\\NRC\\MONDILY.RPF

e APPENDIX C OPERATING DATA REPORT DOCKET NO.

50-265 UNIT Two DATE May 5,1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 040195

1. REPORTING PERIOD; 2400 043095 GROSS HOURS IN REPORTING PERIOD: 719

2. CURRENTLY AIKHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPA :.Y: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY)(MWe-Net): N/A

4. REASONS FOR RESTRICTION (IF ANY):

THis MONTH YR TO DATE CUMULATIVE I

5. NUMBER OF IIOURS REACTOR WAS CRTTICAL 0.00 1516.90 151292.75

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 0.00 1514.90 147446.55

8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

9. GROSS TIIERMAL ENERGY GENERATED (MWli) 0.00 3363599.00 319304303.10

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 1064371.00 102578272.00 11, NET ELECTRICAL ENERGY GENERATED (MWH) 0.00 1012484.00 97168393.00

12. REACTOR SERVICE FACTOR 0.00 52.69 75.46

12. REACTOR AVAILABILITY FACTOR 0.00 52.69 76.95

14. UNrr SERVICE FACTOR 0.00 52.62 73.54

15. UNIT AVAILABILITY FACTOR 0.00 52.62 73.89

16. UNrr CAPACITY FACTOR (Using MDC) 0.00 45.73 63.02

17. UNIT CAPACTTY FACTOR (Using Design MWe) 0.00 44.57 61.43

18. UNIT FORCED OlITAGE RATE 0.00 0.00 9.84

19. SilUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: 6-5-95

21. UNTTS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRTTICALITY INTTIAL ELECTRICTTY COMMERCIAL OPERATION I

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 UNIT One DATE May 5. 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH April 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

781 17.

783 2.

735 18.

784 3.

782 19.

782 4.

785 20.

783 5.

784 21.

780 6.

783 22.

751 7.

783 23.

734 8.

750 24.

782 9.

783 25.

782 10.

767 26.

781 11.

782 27.

780 12.

782 28.

768 13.

784 29.

746 14.

786 30.

783 15.

722 31.

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785 INSTRULi10NS On this form, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt. These figures will be used to plot a graph for each reporting month.

Note that when maximum dependable capacity is used for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line).

In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

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o APPENDIX B AVERAGE DAILY UNIT POWER LEVEL-DOCKET N0 50-265 UNIT Two DATE May 5. 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH April 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

-8 17.

-8 2.

-8 18.

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3.

-8 19.

-8 4.

-8 20.

-8 5.

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-8 24.

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-8 25.

-8 10.

-8 26.

-8 11.

-8 27.

-8 12.

-8 28.

-8 13.

-8 29.

-8 14.

-8 30.

-8 15.

-8 31.

16.

-8 INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt. These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or j

the restricted power level line).

In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

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s APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-254 UNIT NAME One COMPLETED BY Kristal Moore DATE May 5, 1995 REPORT MONTH April 1995 TELEPHONE 309-654-2241 m!!!

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DURATION EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS None for the Month of April.

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a APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE May 5.

1995 REPORT MONTH April 1995 TELEPHONE 309-654-2241 e

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EVENT CORRECTIVE ACTIONS / COMMENTS NO.

DATE (HOURS)

REPORT 95 05 0441-95 5

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4 Continued Refuel Outage Q2R13, TECHOP3\\NRC\\ MONTH 1.Y.RPT

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o VI. UNIOVE REPORTING RE0VIREMENTS The following items are included in this report based on prior commitments to the commission:

A.

Main Steam Relief Valve Operations There were no Main Steam Relief Valve Operations for the reporting period.

B.

Control Rod Drive Scram Timina Data for Units One and Two The basis for reporting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifications 4.3.C.1 and 4.3.C.2.

The following table is a complete summary of Units One and Two Control Rod Drive Scram timing for the reporting period. All scram timing as performed with reactor pressure greater than 800 PSIG.

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RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON. UNIT 1 G 2 CONTROL 4

ROD DRIVES, FROM 01/01/95 TO 12/31/95

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Technical Specification 3.3.C.1 &

DATE

! OF RODS

! O.375 ! O.900 2.00 3.5 7 sec.

3.3.C.2 (Averaae Scram Insertion Timel l:

I 01/15/95 177 l 0.31

! 0.70 1.47 2.57 3.30 Post Maintenance after Q1F35 Seq A, B, Done i

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1 l 0.29 l 0.65 1.42 2.48 2.48 l Q18840 to torque Scram Inlet Valve Packing.

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.e-VII.

REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E.

O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities ~ and Zion Station--NRC Request for Refueling Information", dated January.18, 1978.

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QTP 300-S32 Revision 2-QUAD CITIES REFUELING October-1989 INFORMATION REQUEST 1.

Unit:

' Q1 Reload:

13 14 Cycle:

2.

Scheduled date for next refueling shutdown:

2/5/96 3.

Scheduled date for restart following refueling:

5/15/96 4.

Will refueling or resumption of operation thereafter require a Technical Specification change or other Ilconse amendment:

NO i

5.

Scheduled dr.tst.s) for submitting proposed licensing action and l

supporting information:

7-4-95 6.

Important Ilconsing considerations associated with refueling, e.g., new or different fuel design or supplier, u1 reviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

200 GE10 Fuel Bundles will be loaded during Q1R14.

7.

The number of fuel assemblies.

a.

Number of assemblies in core:

724 1

b.

Number of assemblies in spent fuel pool:

1717 8.

The present Ilcensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:

a.

Licensed storage capacity for spent fuel:

3657 b.

Planned increase in licensed storage:

0 9.

Theprojecteddateofthelastrefuelingthatcanbedischargedtothe spent fuel pool assuming the present licensed capacity: 200 APPROVED i

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QUA0 CITIES REFUELING October 1989 INFORMATION RE0 VEST 1.

Unit:

Q2 Reload:

13 14 Cycle:

2.

Scheduled date for next refueling shutdown:

3-5-95 3.

Scheduled date for restart following refucilng:

6-5-95 4.

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:

NO S.

Scheduled date(s) for submitting proposed licensing action and supporting information:

Approved June 10, 1994 6.

Important licensing considerations associated _with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

144 GE10 Fuel Bundles will be loaded during Q2R13.

7.

The number of fuel assemblies.

a.

Number of assemblies in core:

0 b.

Number of assemblies in spent fuel pool:

3451 8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:

a.

Licensed storage capacity for spent fuel:

3897 b.

Planned increase in licensed storage:

0 9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2006 APPROVED i

(final)

@ 10 N 14/0395t G.C.O.S.R.

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